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Design basis accident
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#	Item
1	Generic Design Assessment - Step 4 Fault Studies - Containment and Severe Accident Design Basis Westinghouse AP1000 Assessment Report Add to Reading List Source URL: www.onr.org.uk Language: English - Date: 2014-08-14 04:57:10
2	Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code 1 2 Add to Reading List Source URL: www.nss.si Language: English - Date: 2015-02-07 16:50:28
3	2. Design Basis Accidents of control rod channel cooling system. Single or multiple main circulation pump trip are examples of loss-of-flow transients. Loss-of-coolant accidents include full or partial breaks of group di Add to Reading List Source URL: www.lei.lt Language: English - Date: 2010-04-09 09:09:17 Energy conversion Nuclear reactors Nuclear reactor safety systems Light water reactors RBMK Loss-of-coolant accident Nuclear power plant Nuclear reactor Auxiliary feedwater Nuclear technology Energy Nuclear safety
4	Draft Decree of the Nuclear Regulatory Authority of the Slovak Republic of, on nuclear safety requirements The Nuclear Regulatory Authority of the Slovak Republic (hereinafter the "Authority"), pursuant to Add to Reading List Source URL: www.ujd.gov.sk Language: English - Date: 2011-12-11 12:41:02 Energy conversion Nuclear technology Radioactivity Nuclear power Design basis accident Nuclear reactor Radioactive waste Containment building International Nuclear Event Scale Energy Nuclear physics Nuclear safety
5	Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code 1 2 Add to Reading List Source URL: www.djs.si Language: English - Date: 2015-02-07 16:50:28 Pressurizer Small modular reactor Reactor protection system Loss-of-coolant accident Boiling water reactor safety systems B&W mPower Nuclear technology Energy Nuclear safety
6	Microsoft Word - DOE-STD-3009 Concurrence VersionCLEAN.docx Add to Reading List Source URL: www.efcog.org Language: English - Date: 2015-01-23 16:34:57 Safety engineering Nuclear safety Nuclear accidents Occupational safety and health Industrial hygiene Hazard analysis Design basis accident Radioactive contamination International Nuclear Event Scale Safety Nuclear physics Nuclear technology
7	Improvement of Severe Accident Management for Indian NPPs Deb MUKHOPADHYAY Reactor Safety Division Rector Design & Development Group Bhabha Atomic Research Centre Add to Reading List Source URL: www-pub.iaea.org Language: English - Date: 2014-03-20 09:01:10 Nuclear accidents Tokyo Electric Power Company Radioactivity Fukushima Daiichi Nuclear Power Plant Tōhoku region International Nuclear Event Scale Nuclear power Design basis accident Fukushima Daiichi nuclear disaster Energy Nuclear physics Nuclear safety
8	AERB NPP-LWR SC D[removed]pmd Add to Reading List Source URL: www.aerb.gov.in Language: English - Date: 2015-03-10 06:53:41 Nuclear safety Atomic Energy Regulatory Board Nuclear energy in India Nuclear power stations Energy conversion Radioactivity Nuclear power plant Nuclear power Design basis accident Nuclear technology Energy Nuclear physics
9	Technical Safety AssesSment Guide SAFETY FLUID SYSTEMS ETSON[removed]March 2015 Add to Reading List Source URL: www.etson.eu Language: English - Date: 2015-03-19 04:51:43 Risk Systems engineering Reliability engineering Nuclear safety Design basis accident Functional Safety IEC 61508 Safety Security Prevention
10	Lessons Learned from the Fukushima Dai-ichi Accident and Responses in New Regulatory Requirements Toyoshi Fuketa Nuclear Regulation Authority International Experts’ Meeting on Severe Accident Management Add to Reading List Source URL: www-pub.iaea.org Language: English - Date: 2014-03-20 09:12:02 Nuclear safety Seismology Design basis accident Radioactivity Probabilistic risk assessment Fukushima Daiichi Nuclear Power Plant Fire safety Nuclear meltdown Earthquake Nuclear technology Nuclear physics Safety

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